Published April 2016 | Version v1
Book Metadata-only

Comparison analysis of source term calculation by using ORIGEN-S and ORIGEN-2

Creators

  • 1. China Nuclear Power Engineering CO., LTD, Beijing (China)
  • 2. North China Electric Power University, Beijing (China)

Description

The fuel assembly and reactor core source term calculating is a basic work to nuclear power plant radiation shielding analysis, which impacts the design of fuel transfer channel, the shielding design of nuclear fuel building, heat exchanging design of fuel storage pool, accident analysis and accident consequence assessment and emergency, and the design of spent fuel shipping cask. ORIGEN-S and ORIGEN-2 are time-dependent burnup analysis codes that usually used for radiation source term calculation. Based on a quarter core annual reloading pattern for equilibrium cycle, ORIGEN-S and ORIGEN-2 are used in this paper to analyze the differences of source term such as activity, decay heat, neutrons and photons spectrum calculated by both codes in order to provide research reference for the source term calculation of spent fuel assemblies and reactor core. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.4). Proceedings of academic annual meeting of China Nuclear Society in 2015, No.5--Radiation Protection sub-volume

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
978-7-5022-7103-9
Imprint Title
Progress report on nuclear science and technology in China (Vol.4). Proceedings of academic annual meeting of China Nuclear Society in 2015, No.5--Radiation Protection sub-volume
Imprint Pagination
252 p.
Journal Page Range
p. 245-252

Conference

Title
2015 academic annual meeting of China Nuclear Society
Dates
21-24 Sep 2015
Place
Mianyang (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
53085179
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT; BURNUP; COMPARATIVE EVALUATIONS; DESIGN; FUEL ASSEMBLIES; FUEL STORAGE POOLS; NEUTRONS; NUCLEAR POWER PLANTS; O CODES; RADIATION SOURCES; REACTOR CORES; SHIELDING; SOURCE TERMS; SPENT FUELS
Descriptors DEC
BARYONS; COMPUTER CODES; ELEMENTARY PARTICLES; ENERGY SOURCES; EVALUATION; FERMIONS; FUELS; HADRONS; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; NUCLEONS; POWER PLANTS; REACTOR COMPONENTS; REACTOR MATERIALS; THERMAL POWER PLANTS

Optional Information

Notes
1 fig., 6 tabs., 6 refs.